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Number 1
Number 2

Number 3
Number 4

Number 1

Table of Contents
On the Calculation of Water Gap Peaking (Gerald P. Calame)
Reactivity Effects of Protactinium-233 Buildup in U²³³ Fast Breeder Reactors (Arthur J. Goldman)
Re: The Application of Statistical Methods of Analysis for Predicting Burnout Heat Flux (W. R. Gambill)
Re: The Application of Statistical Methods of Analysis for Predicting Burnout Heat Flux—Rebuttal (R. T. Jacobs, J. A. Merrill)
Abstract No. 10 (Melvin Tobias, T. B. Fowler)
Abstract No. 9 (F. W. Brinkley, C. B. Mills)
Abstract No. 11 (H. Rief)
SM-2 Flexible Critical Experiments
On the Solution of Transport Problems by Conditional Monte Carlo (D. W. Drawbaugh)

Calculations of the Neutron Age in Water and Heavy Water for D-D Sources
John W. Cooper
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 1-10
Technical Paper | doi.org/10.13182/NSE61-A25922
Age to Indium Resonance for D-D Neutrons in Heavy Water
V. Spiegel, Jr., A. C. B. Richardson
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 11-15
Technical Paper | doi.org/10.13182/NSE61-A25923
Some Calculations on the Age of Neutrons in D₂O
Herbert Goldstein, Jeremiah Certaine
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 16-23
Technical Paper | doi.org/10.13182/NSE61-A25924
Further Results of Irradiation of Uranium Carbide
A. W. Hare, S. Aifant, F. A. Rough, D. I. Slnizer
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 24-30
Technical Paper | doi.org/10.13182/NSE61-A25925
A Two-Mode Variational Procedure for Calculating Thermal Diffusion Theory Parameters
G. P. Calame, F. D. Federighi, P. A. Ombrellaro
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 31-39
Technical Paper | doi.org/10.13182/NSE61-A25926
Hydraulic Studies for the Fluid-Bed Reactor
V. P. Kelly
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 40-44
Technical Paper | doi.org/10.13182/NSE61-A25927
Pulsed Neutron Measurement of Control Rod Worths
O. C. Kolar, F. A. Kloverstrom
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 45-52
Technical Paper | doi.org/10.13182/NSE61-A25928
The Determination of Hydrogen in Uranium by Mass Spectrometry
L. A. Fergason, D. E. Seizinger, C. H. McBride
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 53-56
Technical Paper | doi.org/10.13182/NSE61-A25929
U²³⁸ Epithermal Capture in PWR-1 Blanket Clusters
W. Baer
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 57-60
Technical Paper | doi.org/10.13182/NSE61-A25930
Fast Neutron Energy Spectra in Graphite-Moderated Reactors
Mark T. Robinson, O. S. Oen, D. K. Holmes
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 61-69
Technical Paper | doi.org/10.13182/NSE61-A25931
Determination of Trace Quantities of Fission Products in Nonirradiated Natural and Depleted Uranium Salts
P. K. Kuroda, M. P. Menon
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 70-74
Technical Paper | doi.org/10.13182/NSE61-A25932
Examination of the Range of Applicability of Conditional Monte Carlo to Deep Penetration Problems
S. K. Penny, C. D. Zerby
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 75-82
Technical Paper | doi.org/10.13182/NSE61-A25933
The Fast Effect in Uranium and Beryllium Systems
Herbert Rief
Nuclear Science and Engineering | Volume 10 | Number 1 | May 1961 | Pages 83-89
Technical Paper | doi.org/10.13182/NSE61-A25934

Number 2

Table of Contents
Critical Heat Flux for Water in Swirling Flow (R. Viskanta)
Radioisotope Techniques (Vincent P. Guinn)

An Application of the Reciprocity Theorem to the Acceleration of Monte Carlo Calculations
C. W. Maynard
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 97-101
Technical Paper | doi.org/10.13182/NSE61-A25945
The Single-Scattering Approximation to the Solution of the Gamma-Ray Air-Scattering Problem
D. K. Trubey
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 102-116
Technical Paper | doi.org/10.13182/NSE61-A25946
Slowing Down from an Energy Distributed Neutron Source
A. Keane
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 117-119
Technical Paper | doi.org/10.13182/NSE61-A25947
The Effect of Temperature on Xenon Instability
J. Chernick, G. Lellouche, W. Wollman
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 120-131
Technical Paper | doi.org/10.13182/NSE10-2-120
Spherical Harmonic Calculations for a Cylindrical Cell of Finite Height
N. Tralli, J. Agresta
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 132-141
Technical Paper | doi.org/10.13182/NSE61-A25949
Inelastic Scattering of Neutrons by U²³⁸ below 1 Mev
Lawrence Dresner
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 142-150
Technical Paper | doi.org/10.13182/NSE61-A25950
Investigation on the Inelastic Moderation of Fast Neutrons
C. A. Heusch, T. Springer
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 151-158
Technical Paper | doi.org/10.13182/NSE61-A25951
Minimum Critical Mass in Variable Density and Epithermal Reactors
Mathew M. Shapiro
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 159-162
Technical Paper | doi.org/10.13182/NSE61-A25952
The Solubility of Nickel in Sodium by a Tracer Technique
T. A. Kovacina, R. R. Miller
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 163-166
Technical Paper | doi.org/10.13182/NSE61-A25953
Doppler Broadening of Low-Energy Neutron Resonances
A. W. Solbrig, Jr.
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 167-168
Technical Paper | doi.org/10.13182/NSE61-A25954
Low-Energy Neutron Resonances in Eu¹⁵¹
S. Tassan, A. Hellsten, V. L. Sailor
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 169-172
Technical Paper | doi.org/10.13182/NSE61-A25955
Thermionic Reactor Systems
R. C. Howard
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 173-182
Technical Paper | doi.org/10.13182/NSE61-A25956
Application of Rapid Fission Gas Analyses to an Off-Gas System Test
R. C. Koch, G. L. Grandy, J. A. Roll
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 183-189
Technical Paper | doi.org/10.13182/NSE61-A25957
A Variational Procedure for Determining Spatially Dependent Thermal Spectra
G. P. Calame, F. D. Federighi
Nuclear Science and Engineering | Volume 10 | Number 2 | June 1961 | Pages 190-201
Technical Paper | doi.org/10.13182/NSE61-A25958

Number 3

Table of Contents
Comparative Effects of Radiation (Titus C. Evans)
Abstract No. 14 (M. A. Friedman, P. F. Zweifel)
Abstract No. 15 (C. Eicheldinger)

Few Group Calculations of Thermal Neutron Transport
M. Goldsmith, R. M. Cantwell
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 207-218
Technical Paper | doi.org/10.13182/NSE61-A25962
Exact Solution of the Slowing-Down Equation
Roman Bednarz
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 219-222
Technical Paper | doi.org/10.13182/NSE61-A25963
Temperature Distributions of Reactor Fuel Element End Caps
K. R. Merckx
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 223-227
Technical Paper | doi.org/10.13182/NSE61-A25964
A Suggested Method for the Chemical Reprocessing and Purification of Th—U—O Slurry-Type Reactor Fuels
Donald G. Gardner
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 228-234
Technical Paper | doi.org/10.13182/NSE61-A25965
U²³⁸ Radiative Capture in PWR-2 Blanket Geometry
W. Baer
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 235-239
Technical Paper | doi.org/10.13182/NSE61-A25966
Two-Group Theory of a Ring of N Cylindrical Rods or Zones in a Reflected Reactor
M. S. Trasi
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 240-246
Technical Paper | doi.org/10.13182/NSE61-A25967
Correlation and Predicfion of Explosive Metal-Water Reaction Temperatures
Leo F. Epstein
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 247-253
Technical Paper | doi.org/10.13182/NSE61-A25968
Applications of Geometric Theory to Nonlinear Reactor Dynamics
Elias P. Gyftopoulos
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 254-268
Technical Paper | doi.org/10.13182/NSE61-A25969
Hydrodynamic Models for the Treatment of Reactor Thermal Transients
J. E. Meyer
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 269-277
Technical Paper | doi.org/10.13182/NSE61-A25970
The Connection of Zircaloy-2 with Stainless Steel for Operation over a Wide Temperature Range
C. Gordon Duff
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 278-284
Technical Paper | doi.org/10.13182/NSE61-A25971
Diffusion Lengths in Heterogeneous Media
Joel H. Ferziger, George S. C. Wang, P. F. Zweifel
Nuclear Science and Engineering | Volume 10 | Number 3 | July 1961 | Pages 285-294
Technical Paper | doi.org/10.13182/NSE61-A25972

Number 4

Table of Contents
Spatial Dependence of Thermal-Neutron Spectra and the Interpretation of Thermal Utilization Measurements (Robert W. Deutsch)
Measurements of Relative Pu Fission Rates in Slightly Enriched Uranium—Water Lattices (J. J. Volpe, D. Klein)
Proposed Reactor Radiation Damage Monitor (S. I. Taimuty)
Nuclear Energy in Industry (Titus G. LeClair)
Radiation Hazards and Protection (Lauriston S. Taylor)
Nuclear Data Tables, Part 3; Nuclear Reaction Graphs (Alan B. Smith)
Resonance Absorption in Nuclear Reactors (Norman C. Francis)

Particle Self-Shielding in Plates Loaded with Spherical Poison Particles
W. B. Doub
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 299-307
doi.org/10.13182/NSE61-A15371
Cross Sections of Threshold Reactions for Fission Neutrons: Nickel as a Fast Flux Monitor
T. O. Passell, R. L. Heath
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 308-315
doi.org/10.13182/NSE61-A15372
Formation and Control of Turbidity in Aluminum-Water Reactor Systems
S. R. Hatcher, H. K. Rae
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 316-330
doi.org/10.13182/NSE61-A15373
Nuclear Reactors with Maximum Prompt Neutron Lifetime
J. Ernest Wilkins, Jr.
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 331-336
doi.org/10.13182/NSE61-A15374
Mean Square Instability in Boiling Reactors
A. Z. Akcasu
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 337-345
doi.org/10.13182/NSE61-A15375
A Radiochemical Technique for the Determination of Short-Lived Fission Gases
Charles W. Townley, James E. Howes, Jr., Gilbert E. Raines, Ward S. Diethorn, Duane N. Sttnderman
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 346-351
doi.org/10.13182/NSE61-A15376
Asymptotic Reactor Theory
K. M. Case, Joel H. Ferziger, P. F. Zweifel
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 352-356
doi.org/10.13182/NSE61-A15377
Consistent P₁ Criticality Calculations
P. F. Zweifel, Joel H. Ferziger
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 357-361
doi.org/10.13182/NSE61-A15378
Escape-Probabilities in Asymptotic Reactor Theory
S. Yip, P. F. Zweifel
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 362-366
doi.org/10.13182/NSE61-A15379
Laboratory Development of the Acid Thorex Process For Recovery of Thorium Reactor Fuel
R. H. Rainey, J. G. Moore
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 367-371
doi.org/10.13182/NSE61-A15380
On the Range of Validity of Nonlinear Reactor Dynamics
Elias P. Gyftopoulos, Jacques Devooght
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 372-376
doi.org/10.13182/NSE61-A15381
Comparison of Wilkins Equation with Experiments on Water Systems
Luis de Sobrino, Melville Clark, Jr.
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 377-383
doi.org/10.13182/NSE61-A15382
Comparison of the Wilkins Equation and Higher Order Approximations for Solid Moderators
Luis de Sobrino, Melville Clark, Jr.
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 384-387
doi.org/10.13182/NSE61-A15383
A Study of Wilkins Equation
Luis de Sobrino, Melville Clark, Jr.
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 388-399
doi.org/10.13182/NSE61-A15384